ML20077H161
| ML20077H161 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 07/22/1983 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM P-83257, NUDOCS 8308090637 | |
| Download: ML20077H161 (3) | |
Text
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o 16805 WCR 19 1/2, Platteville, Colorado 80651 July 22, 1983 Fort St. Vrain Unit #1 P-83257 TM@@ JM]!P S
Mr. John T. Collins, Regional Administrator AUG I E
U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 O
Arlington, TX 76012
SUBJECT:
I & E Inspection Report 83-06 Open Items
REFERENCES:
I & E Inspection Reports 78-15, 79-05, 81-28, 82-21 and 83-06
Dear Mr. Collins:
In accordance with the request of your Mr. Wagner to Mr. Borst of my staff on July 19, 1983, please find our evaluation of the current status of the six open unresolved items contained in I & E Inspection Report 83-06.
Unresolved Item 267/8128-01:
Reactor Building Exhaust Filters In spite of an exhaustive search of our records, we have uncovered no do:umentation which would confirm that the required flow distribution testing had in fact been performed. Based on this paucity of data, r pril 21, 1982 the flow distribution testing was performec (and records retained).
Public Service Company (PSC) plans no further action on this item; it is our understanding that the Nuclear Regulatory Commission (NRC) will resolve this item shortly.
Open Item 267/8128-01:
Gaseous Iodine / Particulate and Liquid Monitors Progress on this open item is being tracked via Corrective Action / Action Request-(CAAR)-466. The current target date for completion of PSC action is September 1, 1983.
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+ Open Item 267/8128-02:
Control Room Filter and Technical Support Center Filters Progress on this open item is being tracked via CAAR-479.
Closure of the item is dependent on the completion of Change Notice 1603, issued to the Nuclear Engineering Division. The work entails totally rebuilding the Control Room filter housing.
Work on this item is ongoing.
The Technical Support-Center Filters have been included in a testing program via non-Technical Specification Surveillance SR-HE-4-A, which was successfully run on November 15, 1982.
PSC plans no further action on this portion of Open Item 267/8128-02.
Open Item 267/8221-03:
Primary Coolant Sample Lines /NUREG-0737, Item II. B. 3, "Postaccident Sampling Capability" 1
Progress on this open item was tracked via CAAR-572.
Following an evaluation of the potential for line blockage, activity plate-out, or' sample distortion by the Nuclear Engineering Division, PSC closed the CAAR on April 7, 1983.
We plan no further ~ action on this open item, and recommend that the NRC close'the item.
Open Item 267/8221-05:
Reactor ~ Building Ventilation Exhaust Monitor Progress on this open item was tracked via CAAR-570. Based on an evaluation of the effect of entrained moisture on the zeolite cartridge adsorbers in the iodine sampling system of the reactor building ventilation exhaust effluent stream by the Nuclear Engineering Division, PSC closed this CAAR on April 7, 1983.
We plan.no further action on this open item, and recommend that
-the NRC close the item.
.. Unresolved Item 267/7815-01:
Use of Reactor Building Sump for Processing Radioactive Liquids This item was originally opened by the NRC in I & E Inspection Report 78-15, was subsequently -closed by the NRC in I & E Inspection Report 79-05, and subsequently reor,ened by the-NRC in I & E Inspection Report 81-28. Assuming that the item is still open, progress on the. item is being tracked via CAAR-610.
Although the CAAR is currently open with a target date of August 1, 1983,- PSC action on this item has been completed, by:
1.
Amending -the Fort St. Vrain Final Safety Analysis Report to include the above application for the Reactor Building Sump.
This update was sent to you via P-83242, dated July 13, 1983.
2.
Performing a safety evaluation of the above application of the Reactor Building Sump. This. evaluation was completea on July 12, 1983, and is available for review by the NRC.
Based on the above steps, we will take steps to'close-1 CAAR-610, and we plan no additional actions, other than recommending that the NRC close this item.
As you can see, we have taken and are taking appropriate action to close the.above items.
Your prompt action on recommended closure will be appreciated.
If you should have any additional questions on the'above items please contact Mr. Ted Borst at -(303) 785-2223, ext. 203.
On another subject, please note that. figure 2 of P-82423 is
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mislabled.
The ordinate of the figure should read mrem, not rem. We regret any confusion this may have caused.
Very truly yours, On W. W. n n 6. m "P):Af 1rje4A l.
Don W. Warembourg Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station i-DWW/djc cc:
Phil Wagner, R IV, NRC G. L. Plumlee, III, Senior Resident Inspector, FSV l
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